Nuclear fuel assembly having identification codes

ABSTRACT

A nuclear fuel assembly having first and second nuclear fuel identification codes marked on the fuel assembly. The first nuclear fuel identification code is of a different expression than the second nuclear fuel identification code and is arranged adjacent thereto.

This application is a divisional of application Ser. No. 346,226 filedMay 2, 1989, now U.S. Pat. No. 5,089,213.

BACKGROUND OF THE INVENTION

The present invention relates to a nuclear fuel identification codereader and a fuel assembly, and more particularly to a nuclear fuelidentification reader and a fuel assembly which are suitable foridentification of a fuel assembly in a fuel storage pool.

In the past, the identification of a nuclear fuel identification numberof a fuel assembly loaded into a fuel storage pool has been effected byan operator by watching on a television monitor a video image taken by amarine TV camera. This is reported in Nuclear Technology, Vol. 72, March1986, pp. 321-327.

In the prior art method in which the video image of the TV camera ismonitored through the TV monitor, there are some cases where it is notpossible to identify the fuel identification number marked on the fuelassembly if clad (soft clad primarily consisting of Fe₂ O₃) is depositedon the fuel assembly.

A solution to the above problem is disclosed in JP-A-57-53688,particulary FIG. 4 thereof. Eddy current sensors are inserted intorecesses formed on a top surface of a handle of the fuel assembly todetect the fuel identification number.

JP-A-60-207095 and JP-A-57-110994 disclose techniques to identify thefuel assembly by detecting a mark such as a groove formed at a top ofthe fuel assembly by ultrasonic wave.

SUMMARY OF THE INVENTION

It is an object of the present invention to provide a nuclear fuelidentification code reader capable of identifying a nuclear fuelidentification code marked on a fuel assembly in a short time and with ahigh accuracy.

It is another object of the present invention to provide a nuclear fuelidentification code reader capable of checking loss of a fuel assemblystored in a fuel storage pool.

It is other object of the present invention to provide a nuclear fuelidentification code reader capable of checking the presence of nuclearfuel in a stored fuel assembly.

The first characteristic feature of the present invention resides in theprovision of an optical sensor and an ultrasonic wave sensor fordetecting the nuclear fuel identification code, means for identify thenuclear fuel identification code based on the information derived fromthe optical sensor, and means for identifying the nuclear fuelidentification code based on the information derived from the ultrasonicwave sensor. In this arrangement, the nuclear fuel identification codecan be identified in a short time.

The second characteristic feature of the present invention resides inthe provision of means for comparing a current recognition result forthe nuclear fuel identification code with a past recognition resulttherefor. Thus, any loss of the stored fuel assembly can be checked.

The third characteristic feature of the present invention resides in theprovision of means for photographing a Chelencoff light generated in thefuel assembly and means for image processing an image signal of theChelencoff light photographed by said photographing means. Thus, thepresence of the nuclear fuel in the stored fuel assembly can be readilychecked.

BRIEF DESCRIPTION OF THE DRAWINGS

FIG. 1 shows one embodiment of a nuclear fuel identification code readerof the present invention,

FIG. 2 shows an enlarged view of a portion II in FIGS. 1, 16 and 22,

FIG. 3 shows a detailed block diagram of a nuclear fuel handling controlunit, a nuclear fuel identification code monitor and a nuclear fuelidentification code processing unit of FIG. 1,

FIG. 4 shows a perspective view of a fuel assembly of FIG. 1,

FIG. 5 shows a plan view of a handle of FIG. 4,

FIG. 6 shows a VI--VI sectional view of FIG. 5,

FIG. 7 illustrates a standard digital pattern of a nuclear fuelidentification code of FIG. 5,

FIG. 8 shows a processing of fuel monitor control means of FIG. 3,

FIG. 9 shows a processing process of an image processing means 31 ofFIG. 3,

FIG. 10 shows a processing process of a fuel numberidentification/discrimination means of FIG. 3,

FIG. 11 shows a detected character pattern and a standard characterpattern,

FIG. 12 shows a processing process of a probe scan mechanism controlmeans,

FIG. 13 shows a reflected wave received by an ultrasonic wave probe 9 ofFIG. 2,

FIG. 14 shows a processing process of an ultrasonic wave signalprocessing means of FIG. 3,

FIG. 15 shows a processing process of a fuel number identification meansof FIG. 3,

FIGS. 16, 22 and 32 show other embodiments of the nuclear fuelidentification code reader of the present invention,

FIG. 17 shows a block diagram of a nuclear fuel handling control unit, anuclear fuel identification code monitor and a nuclear fuelidentification code illumination unit of FIG. 16,

FIG. 18 shows a block diagram of another embodiment of FIG. 3,

FIG. 19 shows another embodiment of a microprocessor of FIG. 3,

FIG. 20 shows another embodiment of the microprocessor of FIG. 3,

FIG. 21 shows another embodiment of a recess formed in a handle of thefuel assembly,

FIG. 23 shows a detailed block diagram of a nuclear fuel handlingcontrol unit, a nuclear fuel identification code monitor and a dataprocessing unit of FIG. 22,

FIG. 24 shows a processing process of a nuclear fuel detector controlmeans of FIG. 23,

FIG. 25 shows a processing process of an image processing means of FIG.23,

FIG. 26 shows a characteristic chart of a brightness rank and afrequency,

FIG. 27 shows a processing process of a fuel numberidentification/discrimination means of FIG. 23,

FIG. 28 shows a processing process of an ultrasonic wave signalprocessing means of FIG. 23,

FIG. 29 shows a focused ultrasonic wave beam,

FIG. 30(A) and 30(B) illustrate a status of a reflected wave signal,

FIG. 31 shows a processing process of a fuel number identification meansof FIG. 23,

FIG. 33 shows a detailed block diagram of a nuclear fuel handlingcontrol unit, a nuclear fuel monitor and a data processing unit of FIG.32,

FIG. 34 shows a processing process of a nuclear fuel detector controlmeans of FIG. 33,

FIG. 35 shows a processing process of an image processing means of FIG.33,

FIG. 36 shows a processing process of a nuclear fuel data processingmeans of FIG. 33,

FIG. 37 shows a fuel rod layout pattern prepared in a step 79Q of FIG.36,

FIG. 38 shows a photographing status of a Chelencoff light photographingcamera capable of producing a fuel rod layout pattern without generatingan image of a handle,

FIG. 39A shows a fuel rod layout pattern produced by the method of FIG.38,

FIGS. 39B and 39C show fuel rod layout patterns derived from videosignals photographed in directions G₁ and G₂ in FIG. 38, and

FIGS. 40A and 40B show other embodiments of an optical sensor of FIG. 2.

DESCRIPTION OF THE PREFERRED EMBODIMENTS

The present invention was made based on the study of the techniquesdisclosed in JP-A-57-53688 and JP-A-60-207095.

In the eddy current sensor disclosed in JP-A-57-53688, a detectionaccuracy of the sensor is lowered when a groove narrower than a diameterof the eddy current sensor or a hole having a narrower diameter than thediameter of the eddy current sensor is to be detected. Characters of 8mm square size are engraved in a handle of a fuel assembly. A width ofthose curved characters is as narrow as approximately 1.6 mm.Accordingly, the detection accuracy of the nuclear fuel identificationnumber by the eddy current sensor is low. Since the diameter of the eddycurrent sensor is usually approximately 5-10 mm, the reduction of thedetection accuracy is inevitable.

In the ultrasonic wave sensor disclosed in JP-A-60-207095, a signalprocessing time for detecting the nuclear fuel identification number islong and it is difficult to apply the sensor to a number of fuelassemblies in a fuel storage pool, which require a short response time.This is also true in a case where an eddy current sensor having a longsignal processing time is used. JP-A-57-110994 is similar toJP-A-60-207095.

The present invention is intended to solve those problems.

One embodiment of the nuclear fuel identification code reader of thepresent invention is now explained with reference to FIGS. 1, 2 and 3.The nuclear fuel identification code reader of the present embodimentcomprises a sensor handling unit 1, an ITV camera 5, an ultrasonic waveprobe 9, an ultrasonic wave probe scanner 10, a nuclear fuel handlingcontrol unit 22, a nuclear fuel identification code monitor 28 and anuclear fuel identification code processing unit 43. The sensor handlingunit 1 utilizes a portion of a nuclear fuel handling unit 51.

The nuclear fuel handling unit 51 is used to move a used fuel assembly66 in a fuel storage pool 63. The used fuel assembly 66 is taken out ofa core of a nuclear reactor and loaded and stored in a fuel rack 65arranged in the fuel storage pool 63. The fuel storage pool 63 is filledwith water 64. The fuel rack 65 is arranged under a water level of thewater 64. The nuclear fuel handling unit 51 is constructed to cross thefuel storage pool 63. The nuclear fuel handling unit 51 includes amovable truck 52, a laterally movable truck 53, a grapple 54, a clamp 55and a hoist 56. The movable truck 52 is driven by a drive motor 58 on apair of rails 57 arranged on both sides of the fuel storage pool 63. Thelaterally movable truck 53 has the grapple 54, the clamp 55 and thehoist 56 and is driven by a drive motor 60 on a pair of rails 59arranged on the movable truck 52. The grapple 54 is raised and fallen bythe hoist 56 and a drive motor 62. The grapple 54 is rotated by a drivemotor 61 to allow adjustment of an angle of the clamp 55 in a horizontalplane. The drive motor 61 is mounted on the laterally movable truck 53.The grapple 54 is constructed by several linked expandable pipes. Thelamp 55 is mounted at the bottom end of the grapple 54. A direction ofmovement of the movable truck 52 is represented by X, a direction ofmovement of the laterally movable truck 53 is Y, the elevation of thegrapple 54 is represented by Z₁ and the rotation is represented by θ₁.Position signals representing the displacements X, Y, Z₁ and θ₁ aredetected by synchronous signal generators (not shown) mounted on therespective drive shafts of the fuel handling unit 51.

The sensor handling unit 1 has a hoist 2, a drive motor 3 and a grapple4. The hoist 2, the drive motor 3 and the grapple 4 are mounted on themovable truck 53. A drive motor (not shown) which corresponds to thedrive motor 61 and serves to rotate the grapple 4 is mounted on thelaterally movable truck 53. The grapple 4 is also constructed by severallinked expandable pipes. The grapple 4 is moved up and down by the hoist2 and the drive motor 3. The elevation of the grapple 4 is representedby Z₂ and the rotation is represented by θ₂. Position signalsrepresenting the displacements Z₂ and θ₂ are detected by synchronoussignal generators (not shown) mounted on the respective drive shafts ofthe sensor handling unit 1.

A mount table 6 is arranged at the bottom end of the grapple 4. The ITVcamera 5 is mounted on the mount table 6. Four downwardly extendingframes 7 are fixed to the mount table 6 by screws. An illuminationdevice 8 is arranged at the bottom ends of the frames 7. The ultrasonicwave probe scanner 10 is mounted on the mounted table 6 by an arm 11.

A detailed structure of the ultrasonic wave probe scanner 10 isexplained below. A drive motor 13 is mounted at a top of a bottom-openedbox 12. An upwardly extending rotary screw 14 linked to a rotation shaftof the drive motor 13 meshes with a nut (not shown) mounted on a supportmember 16 which is mounted on the arm 11. A pair of guide members 15Aand 15B which hold the rotary screw 14 therebetween are mounted on thedrive motor 13. The guide members 15A and 15B extend through the supportmember 16 so that they are vertically movable. Another drive motor 17 ismounted on a side of the box 12 which faces the ITV camera 5. A rotaryscrew 18 horizontally arranged in the box 12 has one end thereof linkedto a rotation shaft of the drive motor 17 and the other end thereofsupported by a bearing (not shown) mounted on the side of the box 12. Aprobe holding table 19 engages with the rotary screw 18. Two ultrasonicwave probes 9 are mounted on the probe holding table 19. They arearranged to traverse the rotary screw 18. A pair of fixing guides 21 isarranged in the box 12. An encoder 20 measures the displacement of theultrasonic wave probe 9 along the axis of the rotating screw 18.

The ITV camera 5 and the ultrasonic wave probe 9 constitute a nuclearfuel identification code detection means.

The nuclear fuel handling control unit 22 comprises input/output means23A and 23B, a nuclear fuel handling unit control means 24, a nuclearfuel monitor unit control means 25, a memory 26 and a console panel 27.The input/output means 23A supplies control signals to the drive motors58, 60, 61 and 62 and receives the position signals representing thedisplacements X, Y, Z₁ and θ₁ from the corresponding synchronous signalgenerators (not shown). The input/output means 23B supplies controlsignals to the drive motors 3, 58 and 60 and the drive motor (not shown)which drives the grapple 4, and receives the position signalsrepresenting the displacements X, Y, Z₂ and θ₂ from the correspondingsynchronous signal generators (not shown). The input/ output means 23Ainputs and outputs the signals related to the nuclear fuel handling unitcontrol means 24, and the input/output means 23B inputs and outputs thesignals related to the nuclear fuel monitor unit control means 25. Thenuclear fuel handling unit control means 24 and the nuclear fuel monitorcontrol means 25 are included in a computer 48.

The nuclear fuel identification code monitor 28 has a video signaldigitizer 29 and a signal processing microprocessor 30. Themicroprocessor 30 has a memory 33, an image processing means 31 and anuclear fuel number identification/discrimination means 32. The videosignal digitizer 29 is a kind of A/D converter which converts a videosignal (analog signal) sent from the ITV camera 5 to a digital signal.The video signal digitizer 29. The image signal processing means 31 andthe fuel number identification/discrimination means 32 are coupled tothe input/output means 23B. The nuclear fuel identification code monitor28 thus constructed identifies the nuclear fuel identification codebased on the video signal derived from the ITV camera 5.

The nuclear fuel identification code monitor 34 comprises a pulsegeneration means 35, a signal receive means 36, a probe scanner controlmeans 38 which is constructed by a microprocessor, and a signalprocessing microprocessor 39. The microprocessor 39 has an ultrasonicwave signal processing means 40, a nuclear fuel number identificationmeans 41, and a memory 42. The pulse generation means 35 is connected tothe ultrasonic wave probe 9 and the probe scanner control means 38. Thesignal receive means 36 is connected to the ultrasonic wave probe 9 andthe ultrasonic wave signal processing means 40. The ultrasonic wavesignal processing means 40 is coupled to the encoder 20. The probescanner control means 38 is connected to the drive motors 13 and 17, theencoder 20 and a limit switch 37, and further to the input/output means23B. The nuclear fuel identification code monitor 34 thus constructedidentifies the nuclear fuel identification code based on the reflectedwave of the ultrasonic wave derived from the ultrasonic wave probe 9.

The nuclear fuel identification code processing unit 43 comprises a fuelnumber processing means 44 and a memory 45. A numeral 46 denotes adisplay and a numeral 47 denotes a printer. The display 46 may bemounted on the console panel 27.

A structure of the fuel assembly 66 loaded in the fuel rack 65 isexplained with reference to FIG. 4. The fuel assembly 66 loaded in thefuel rack 65 is an assembly of used fuel which is taken out of a centerof a boiled-water type nuclear reactor. The fuel assembly 66 comprisesan upper tie plate 67, a lower tie plate 69, a plurality of fuel rods 70and a plurality of fuel spacers 71. The top and bottom ends of the fuelrods 70 are held by the upper tie plate 67 and the lower tie plate 69.The fuel spacers 71 are arranged axially of the fuel assembly 66 to keepa predetermined spacing between the fuel rods 70. A channel box 72mounted on the upper tie plate 67 surrounds a bundle of fuel rods 70supported by the fuel spacers 71. The upper tie plate 67 has a handle 72arranged at the top thereof. A nuclear fuel identification number 74 ismarked on the top 73 of the handle 72. As shown in FIGS. 5 and 6, thenuclear fuel identification number 74 includes a nuclear fuelidentification number 74A coded by recesses 75 having circularcross-sections, and a nuclear fuel identification number 74B which is acombination of alphanumeric characters. Those two types of nuclear fuelidentification numbers are marked in parallel on the top 73 of thehandle 72. The nuclear fuel identification number 74B can be recognizedby a human when he/she looks it but the nuclear fuel identificationnumber 74A cannot be recognized by the human by just looking it. Both ofthe nuclear fuel identification numbers 74A and 74B are marked byengraving on the top 73 of the handle 72. The nuclear fuelidentification number 74A is a combination of the recesses 75 whichcorresponds to the nuclear fuel identification number 74B. Thecross-section of the recess 75 need not necessary be circular but it maybe trianglar, square or rectangular, or even oval. In the nuclear fuelidentification number 74A, each area sectioned by broken lines 76corresponds to one character. In FIG. 5, the nuclear fuel identificationnumber 74A represents "2FABC". Each coded symbol of the nuclear fuelidentification number 74A is represented by the combination of up to sixrecesses 75 (two lines of three recesses). Each symbol of the nuclearfuel identification number 74A is a digital signal represented by thepresence or absence of the recess 75. FIG. 7 shows a correspondencebetween the digitized symbols representing the nuclear fuelidentification number 74A and the alphanumeric characters (0-9, A-Z). InFIG. 7, the black dot represents the presence of the recess 75 and awhite dot represents the absence of the recess 75. It is possible todigitize 36 alphanumeric characters by arranging six recesses 75 (twolines of three recesses) as shown in FIG. 7. A plurality of digitalsymbols shown in FIG. 7 may be arranged on the top 73 in combinationwith the characters of the nuclear fuel identification number 74B.Assuming that a diameter of the recess 75 is approximately 1 mm and aspacing W₁ between the recesses 75 in one digital symbol is at leastapproximately 1 mm, the presence or absence of the recess 75 can bedetected by the ultrasonic wave. Since a spacing W₂ between lines ofrecesses 75 is approximately 3 mm, the nuclear fuel identificationnumber 74A and the nuclear fuel identification number 74B can be markedin parallel on the top 73 having a width of approximately 12 mm.

A recess 76 which is used as a reference to read the nuclear fuelidentification number 74A is formed on the top 73 of the handle 72. Therecess 76 is orthogonal to the side of the handle 72 and it ispositioned on the left of the first digital symbol of the nuclear fuelidentification number 74A. Without the recess 76, the nuclear fuelidentification code monitor 34 cannot specify the nuclear fuelidentification number 74A detected by the ultrasonic wave. In theexample shown in FIG. 5, the nuclear fuel identification number 74A maybe read as either "2FABC" or "CBAF2". If it is determined that thenuclear fuel identification number 74A is to be read from the endadjacent to the recess 76, the number 74 is read as "2FABC". A width Wof the recess 76 is either wider or narrower than a width W₄ (diameter)of the recess 75 so that the nuclear fuel identification code monitor 34can easily discriminate the recess 75 of the digital symbol and therecess 76 of the read reference. The recess 76 need not be linear but itmay be circular, triangular or square in cross-section so long as it ispositioned on the left of the lines of recesses 75.

The fuel assembly 66 having the nuclear fuel identification numbers 74Aand 74B marked in parallel on the top 73 of the handle 72 is loaded intothe center of the boiled-water type nuclear reactor after the used fuelassembly 66 has been removed from the center of the reactor.

The operation of the nuclear fuel identification code reader of thepresent invention is non explained.

An operator specifies, through the console panel 27, the operation ofthe nuclear fuel handling or the operation of the detector for thenuclear fuel identification code. The specified operation signal issupplied to the computer 48. If the former operation is specified, thenuclear fuel handling unit control means 24 is activated, and if thelatter operation is specified, the nuclear fuel monitor control means 25is activated.

It is now assumed that the specified operation is the operation ofnuclear fuel handling. Before the function of the nuclear fuel handlingunit control means 24 is explained, the operation of the nuclear fuelhandling unit 51 in the nuclear fuel handling operation is brieflyexplained. A plurality of used free assemblies 66 are carried to apredetermined position in the fuel storage pool 63 from the top thereofwhile they are loaded in a container. Then, the movable truck 52 and thelaterally movable truck 53 are driven to move the clamp 55 above thecontainer. As the grapple 54 descends, the clamp 55 is lowered to theposition of the handle 72 of the fuel assembly 66 in the container.After the clamp 55 has held the handle 72, the grapple 54 is raised.When the bottom end of the fuel assembly 66 reaches a level which is apredetermined distance above the top end of the fuel rack 65, theelevation of the grapple 54 is stopped. The movable truck 52 and thelaterally movable truck 53 are again driven to move the fuel assembly 16to a level which is a predetermined distance (specified by the operatorthrough the console panel 27) above the fuel rack 65. When it reachesthat level, the grapple 54 is lowered to load the fuel assembly 66 to apredetermined position in the fuel rack 65. The above movement isreferred as a movement 1. When the fuel assembly is taken out of thefuel storage pool 63 for fuel processing, the opposite movement(movement 2) is carried out. Namely, the fuel assembly 66 taken out ofthe fuel rack 65 is loaded into the container. The clamp 55 may bemoved, while it does not clamp the fuel assembly 66, from the positionof the fuel rack 65 to other position (movement 3), from the position ofthe fuel rack 65 to the position of the container (movement 4), or fromthe position of the container to the position of the fuel rack 65(movement 5).

The memory 26 stores data relating to the loading status of the fuelassembly 66 at the respective positions (X-Y ID coordinate) of the fuelrack 65. The memory 26 stores "0" for the position at which the fuelassembly 66 is not loaded, and "1" for the position at which the fuelassembly 66 is loaded. The ID coordinate is not represented by absolutedistances on X and Y axises but it is represented by the code applied tothe fuel assembly load position.

The position signals representing the displacements X, Y, Z₁ and θ₁measured by the synchronous signal generators are converted to thedigital signals by the input/output means 23A and they are supplied tothe nuclear fuel handling unit control means 24 of the computer 48. Alimit switch (not shown) mounted on the nuclear fuel handling unit 51detects when the grapple 55 reaches a grapple upper limit level A and amount level B of the fuel assembly (in the fuel rack 65 and thecontainer). The detection signal is supplied to the computer 48. Thenuclear fuel handling unit control means 24 uses those signals tocontrol and monitor the position of the nuclear fuel handling unit 51.

When the used fuel assembly 66 is to be moved in the fuel storage pool63, the operator specifies N target positions (X-Y ID coordinate)necessary for the fuel handling unit 51 to move the fuel assembly 66,through the console panel 27. The P_(l) or P which is shown inJP-B-58-21238, column 6, lines 8-10 is also specified through theconsole panel 27. The nuclear fuel handling unit control means 24discriminates in the manner described and shown in JP-B-58-21238, column7, line 26 to column 8, line 11 and FIGS. 3 and 4. That is, the loadstatus of the fuel assembly 66 at the target position, the correctnessof the data (P_(l) or P) specified by the operator and the open/closestatus of the clamp 55 are checked, and if the check result is normal,the control signal for the corresponding movement (one of the movements1-5) is supplied to the nuclear fuel handling unit 51 to control thecorresponding movement. If the check result is not normal, the nuclearfuel handling unit control means 24 inhibits the start of the nuclearfuel handling unit 51. When the fuel assembly 66 is moved by the nuclearfuel handling unit 51, the data on the load status of the fuel assembly66 at the respective positions of the fuel rack 65, which is stored inthe memory 26, is updated as the movement proceeds.

When the operator specifies the operation of the detector for thenuclear fuel identification code, the nuclear fuel monitor unit controlmeans 25 moves the sensor handling unit 1 in accordance with the process(steps 77A-77M) of FIG. 8. This is explained in detail below. When amonitor operation signal is supplied from the console panel 27 (step77A), a step 77B is carried out.

The position signals representing the displacements X, Y, Z₂ and θ₁measured by the respective synchonous signal generators are converted tothe digital signals by the input/output means 23B and they are suppliedto the nuclear fuel monitor control means 25 of the computer 48. LevelsL₁ and L₂ are detected by the limit switch (not shown) mounted on thesensor handling unit 1. Those detection signals are supplied to thenuclear fuel monitor control means 25, which uses those signals tocontrol and monitor the position of the sensor handling unit 1. Thelevel L₁ (FIG. 2) is set at the bottom end of the ITV camera 5 when thenuclear fuel identification number is monitored so that the illuminationdevice 8 does not contact to the top 73 of the handle 72 of the fuelassembly 66 in the fuel rack 65. The level L₂ is set substantially abovethe level L₁, at a position where the ITV camera 5 is positioned whenthe nuclear fuel identification number is not detected. The sequence ofthe fuel assemblies 66 for which the nuclear fuel identification numbersare detected is predetermined and stored in the memory 26. The sequenceis shown in FIG. 1 by a chain line 49 starting at a point K₁. It is inthe order of the positions K_(i) (i=1, 2, . . . n₁) shown in the X-Y IDcoordinate for the fuel rack 65.

In a step 77B, the grapple 4 is lowered, and when the bottom end of theITV camera 5 reaches the level L₁, the descend of the grapple 4 isstopped. Then, i is set to "1" (step 77C). Whether i=n₁ or not ischecked (step 77D). If it is, a step 77E is carried out, and if it isnot, a step 77M is carried out. In a step 77F following to the step 77E,the movable truck 52 and the laterally movable truck 53 are driven sothat the ITV camera 5 reaches on the fuel assembly 66 which is at theposition K_(i) for which the nuclear fuel identification number is to bedetected. When i=1, the ITV camera 5 is set to the start position K₁.When the ITV camera 5 reaches the position K_(i), a start of detectionsignal S₁ for the nuclear fuel identification number 74B by the ITVcamera 5 is produced (step 77G). The start of detection signal S₁ issupplied to the nuclear fuel identification code monitor 28, the ITVcamera 5 and the illumination device 8. When the nuclear fuelidentification code monitor 28 receives the start of detection signalS₁, it starts to receive and process the video signal produced by theITV camera 5. Upon receipt of the signal S₁, the ITV camera 5 starts topick up the image and the illumination device 8 is turned on. The imagepick-up operation of the ITV camera 5 and the turn-on of theillumination device 8 may be started by the input of the signal S₁ atthe position K₁ and continued until the image pick-up at the positionK_(n) is completed, instead of repetitively turning on and off at eachposition. In a step 77H, a discrimination signal J is received. Thediscrimination signal J is produced by the nuclear numberidentification/discrimination means 32 when the processing of the videosignal relating to one fuel assembly 66 is completed in the nuclear fuelidentification code monitor 28. The fuel memberidentification/discrimination means 32 produces a "0" discriminationsignal J when all characters of the fuel identification number 74Bdetected by the ITV camera 5 are recognized by the image processing, andproduces a "1" discrimination signal J when all characters are notrecognized. After the step 77H, whether the discrimination signal J is"1" or "0" is checked (step 77I). If the discrimination signal J is "0",a step 77D is carried out, and if the signal J is "1", a step 77J iscarried out. In the step 77J, the laterally movable truck 53 (or themovable truck 52) is driven to move the ultrasonic wave probe 9 on theposition K_(i). When the ultrasonic wave probe 9 reaches the positionK_(i), a start of detection signal S₂ for the nuclear fuelidentification number 74A by the ultrasonic wave probe 9 is produced(step 77K). The start of detection signal S₂ is supplied to the probescanner control means 38 of the nuclear fuel identification code monitor34 to effect the detection of the nuclear fuel identification number 74Aby the ultrasonic wave probe 9 and the recognition of the nuclear fuelidentification number 74A by the nuclear fuel identification codemonitor 34. The probe scanner control means 38 produces an end ofultrasonic wave scan signal E₁ when the scan of the ultrasonic waveprobe 9 to detect the fuel identification number 74A is over. When thenuclear fuel monitor control unit 25 receives the end signal E₁ (step77L), it carries out the decision of the step 77D. If the decision inthe step 77D is YES, the grapple 4 is elevated to elevate the ITV camera5 to the level L₂ (step 77M). In this manner, the nuclear fuelidentification numbers of all fuel assemblies 66 in the fuel storagepool 63 are monitored.

The nuclear fuel monitor control means 25 drives the ITV camera 5 whichis the optical sensor for the nuclear fuel identification number ontothe fuel assembly 66 under consideration, and when the fuelidentification number 74B detected by the ITV camera 5 is hard to berecognized, the ultrasonic wave probe 9 which is the ultrasonic wavesensor is driven onto the fuel assembly 66 to detect the fuelidentification member 74A.

The operation of the nuclear fuel identification code monitor 28 when itreceives the start of detection signal S₁ produced by the nuclear fuelmonitor unit control means 25 is explained. When the start of detectionsignal S₁ is received, the video signal digitizer 29 starts the A/Dconversion of the video signal for the top 73 of the handle 72 picked upby the ITV camera 5. The image signal converted to the digital signal bythe video signal digitizer 29 is supplied to the memory 33 in 1/30second and stored therein.

The image processing means 31 carries out the process shown in FIG. 9.Upon receipt of the start of detection signal S₁, the image processingmeans 31 receives the video signal stored in the memory 33 (step 78A).It extracts the image signal of the nuclear fuel identification number74B marked on the fuel assembly 66 under consideration, from the inputimage signal (step 78B). The extracted image signal is processed fornoise elimination (step 78C) and contrast enhancement (step 78D). Then,the image signal is binarized to generate character patterns for allcharacters (n₂, n₂ =5 in the present embodiment) of the detected nuclearfuel identification number 74B (step 78E). Those character patterns aregenerated as two-dimension character patterns P_(jk) (l) (j=1-M, k=1-N,l=1-n₂) having M×N picture elements. The n₂ generated character patternsare supplied to the fuel number identification/discrimination means 32in the sequence of the characters of the nuclear fuel identificationnumber 74B (step 78F).

When the nuclear fuel number identification/ discrimination means 32receives the character patterns of the characters of the nuclear fuelidentification number 74B, it carries out a process comprising steps79A-79K shown in FIG. 10. The nuclear fuel numberidentification/discrimination means 32 receives the n₂ characterpatterns P_(jk) (l) (step 79A) and carries out patterns Q_(jk) (m) fromthe memory 33. In the present embodiment, 36 standard character patternsQ_(jk) (m) (m=1-n₃) including 0-9 and A-Z shown in FIG. 11 are stored inthe memory 33, and n₃ =36. Those standard character patterns correspondto the engraved characters of the nuclear fuel identification number74B.

In a step 79E, a similarity I(m) between the character patterns P_(jk)(l) and the n₃ standard character patterns Q_(jk) (m) are calculated inaccordance with a formula (1). ##EQU1##

The similarity I(m) calculated in accordance with the formula (1) is 1.0when the character patterns P_(jk) (l) and the standard characterpatterns Q_(jk) (m) fully match. It does not exceed 1.0. In a step 79F,whether a maximum one (max I(m)) of the I(m) calculated for thecharacter patterns P_(jk) (l) is larger than a predetermined threshold Sor not. When max I(m) is close to 1.0, it indicates that the ITV camera5 has detected the characters of the nuclear fuel identification number74 to a sufficient extent to permit the recognition. When max I(m) isaround 0.6, it means that the characters of the nuclear fuelidentification number 74B cannot be sufficiently detected because of thedeposition of soft clad. The threshold S is to be determined by takingthe above into account.

When max I(m) is smaller than the threshold S (the decision in the step79F is NO), the "1" discrimination signal J is supplied to theinput/output means 23B of the nuclear fuel handling unit control means22 in order to detect the nuclear fuel identification number 74A by theultrasonic probe 9 (step 79K). In the step 79F, the necessity of thedetection of the nuclear fuel identification number 74A by theultrasonic wave sensor, that is, the necessity of the movement of theultrasonic wave probe 9 onto the fuel assembly 66 under consideration ischecked. If the decision in the step 79F is YES, the characters of thecharacter patterns P_(jk) (l) are recognized as the characterscorresponding to the standard character patterns Q_(jk) (m) having thesimilarity max I(m) (step 79G). If the decision in the step 79H is NO,the steps 79C et seq are repeated. If the decision is YES, a step 79I(output of the "0" discrimination signal J) is carried out. The "0"discrimination signal J is also supplied to the input/output means 23B.Finally, the n characters (2FABC) recognized in the step 79J aresupplied to the nuclear fuel number processing means 44 of the nuclearfuel identification code processing unit 43. The character recognitiontechnique carried out by the nuclear fuel numberidentification/discrimination means 32 is a two-dimension templatematching method.

The operation and process of the nuclear fuel identification codemonitor 34 when the nuclear fuel number identification/discriminationmeans 32 produces the "1" discrimination signal J in the step 79K andthe nuclear fuel monitor control means 25 produces the start ofdetection signal S₂ are now explained.

The process of the probe scan control means 38 is shown in FIG. 12. Whenit receives the start of detection signal S₂ (step 80A), it sends adrive signal to the drive motor 13 (step 80B). As the drive motor 13rotates, the rotary screw 14 is rotated and the box 12 whichaccommodates the ultrasonic wave probe 9 is moved down. When the startof detection signal S₂ is generated, the ultrasonic wave probe scanner10 has already been located above the fuel assembly 66 underconsideration. As a result, the handle 72 of the fuel assembly 66 isinserted between the pair of fixing guides 21 in the descending box 12.When the limit switch 37 contacts to the top 73 of the handle 72, itproduces an activation signal. When the probe scanner control means 38receives the activation signal, it stops the rotation of the drive motor13. In a step 80D, a start of ultrasonic wave scan signal S₃ isgenerated. The start signal S₃ is supplied to the pulse generation means35 and the ultrasonic signal processing means 40. When the pulsegeneration means 35 receives the start signal S₃, it produces anelectrical pulse to cause the ultrasonic wave probe 9 to generate anultrasonic wave. The ultrasonic wave generated by the ultrasonic waveprobe 9 is irradiated to the top 73 of the handle 72. After the step80D, a drive signal is supplied to the drive motor 17 (step 80E). As thedrive motor 17 rotates, the rotary screw 18 is rotated and the probesupport table 19 which accommodates the ultrasonic probe 9 is moved fromthe right to the left in FIG. 2. Since the fixing guides 21 contact tothe top 73 of the handle 72, the ultrasonic wave probe 9 is movedlaterally while the distance to the top 73 is kept constant. One of thepair of ultrasonic wave probe 9 mounted on the probe support table 19moves on an extended line of an arrow R₁ (FIG. 5) and the other moves onan extended line of an arrow R₂ which is parallel to the arrow R₁. Inthe present embodiment, the pair of ultrasonic wave probes 9 cansubstantially simultaneously detect the two lines of recesses 75 of thenuclear fuel identification number 74A. When the ultrasonic wave probe 9reaches the end point of scan, it is detected by the encoder 20. Thedetection signal (position signal of the ultrasonic wave probe 9) of theencoder 20 is supplied to the probe scanner control means 38. When theultrasonic wave probe 9 reaches the end point of scan, the probe scannercontrol means 38 stops the drive motor 17 and produces an end ofultrasonic wave scan signal E₁ (step 80E). After the step 80F, it drivesthe drive motor 13 to elevate the ultrasonic wave probe 9 to apredetermined position (step 80G). Then, the detection of the nuclearfuel identification number 74A by the ultrasonic wave probe 9 isterminated.

As described above, the ultrasonic wave probe 9 irradiates theultrasonic wave to the top 73 of the handle 72 and receives thereflected ultrasonic wave from the top 73. A relationship between ahorizontal position of the ultrasonic wave probe 9 driven by the drivemotor 17 and the reflected ultrasonic wave is shown in FIG. 13. Thereflected wave in FIG. 13 is detected by the ultrasonic probe 9 which ismoved on the extended line of the arrow R₁. The ultrasonic wavegenerated by the ultrasonic wave probe 9 is mostly reflected by the areaof the top 73 which has no recess 75, and the reflected ultrasonic waveis received by the ultrasonic wave probe. However, since the bottom ofthe recess 75 is arcuate as shown in FIG. 6, the ultrasonic wave isscattered in the area of recess 75 and little reflected wave reaches theultrasonic wave probe 9. Accordingly, the amplitude of the reflectedwave is zero in the area of recess 75. Clad may deposit on the top 73 ofthe handle 72 of the fuel assembly 66 which the fuel assembly 66 isloaded in the center of the nuclear reactor and a portion of therecesses 75 may be covered by the clad. Even if the recesses 75 on thetop 73 of the handle 72 of the fuel assembly 66 loaded in the fuel rack65 is covered by the clad, it is possible to detect the recesses 75 bythe ultrasonic wave. This is due to the fact that there is nosubstantial difference between acoustic impedances of water andwater-containing clad (primary constituent is ferric oxide). Thereflected wave signal detected by the ultrasonic wave probe 9 issupplied to the signal receive means 36. In the reflected wave signal ofFIG. 13, a zero reflected wave output area having a width W₃ correspondsto the recess 76 which is the read reference recess. Other zeroreflected wave output areas correspond to the recesses 75.

As a method for detecting the digitized recesses 65 of the nuclear fuelidentification number 74A, one of the following methods may beadopted: 1) two-dimensionally scanning one ultrasonic wave probe, 2)linearly scanning a plurality of parallelly arranged ultrasonic waveprobes, and 3) two-dimensionally scanning the ultrasonic wave beam byelectronically switching ultrasonic wave probes by using an array sensorhaving a plurality of ultrasonic wave probes arranged two-dimensionallyto cover the entire area of the nuclear fuel identification number 74A.The present embodiment adopts the method 2).

The signal receive means 36 converts the input reflected wave signal to"1" and "0" pulse signals. The zero reflected wave output is convertedto "1" and non-zero reflected wave output is converted to "0". Theoutput signal (pulse signal) of the signal receive means 36 and theposition signal of the ultrasonic wave probe 9 detected by the encoder20 are supplied to the ultrasonic wave signal processing means 40, whichcarries out a process comprising steps 81A-81E shown in FIG. 14. Thepulse signal corresponding to the read reference recess 76 detected, andthe position of the ultrasonic wave probe 9 where the pulse signal wasgenerated are determined based on the input signals supplied in the step81A (step 81B). The pulse signal corresponding to the recess 76 can bereadily detected because it is narrower (in the area of "1") than thepulse signals corresponding to the recesses 75. The presence or absenceof the recesses 75 is detected and the positions of the recesses 75 aredetermined relative to the recess 76 (step 81C). The pulse signalcorresponding to the recess 75, that is, the pulse signal having thepulse width W₄ is detected and the position of the ultrasonic wave probe9 corresponding to the pulse signal of the pulse width W₄ is determined.Based on the data of the position of the recess 75 determined in thestep 81C, the presence or absence of the recess 75 at six predeterminedpositions is determined in five areas sectioned by the broken lines 76of the nuclear fuel identification number 74A of FIG. 5, and signals "0"or "1" are assigned to the six predetermined positions, with eachpredetermined position being a unit (step 81D). Thus, the digitalpattern signals for the units, which are "1" if the recesses 75 arepresent and "0" if the recesses 75 are not present, are produced. A unitnumber of digital pattern signals corresponding to the number ofcharacters (n₂) of the nuclear fuel identification number 74B aresupplied to the fuel number recognition means 41 in sequence startingfrom the recess 76 (step 81E).

The fuel number recognition means 41 carries out a process comprisingsteps 82A-82C shown in FIG. 15. The memory 42 stores the correspondencebetween the standard digital patterns which represent the presence orabsence of the recesses 75 shown in FIG. 7 and the characters(alphanumeric). The fuel number recognition means 41 reads the standarddigital patterns corresponding to the digital patterns for therespective units received in the step 82A, from the memory 42, andrecognizes the characters corresponding to the standard digital patternsas the characters for the digital pattern signals (step 82B). The fuelnumber recognition means 41 supplies the n₂ characters (2FABC)recognized for the fuel identification number 74A to the fuel numberprocessing means 44 (step 82C).

Thus, the detection of the nuclear fuel identification number marked onthe handle 72 of the fuel assembly 66 by the nuclear fuel identificationcode monitor 28 or 34, and the recognition of the detected nuclear fuelidentification number as characters are terminated.

The fuel number processing means 44 receives the characters of thenuclear fuel identification number recognized by the nuclear fuelidentification code monitor 28 or 34, and the X-Y ID coordinates of thepositions K_(i) based on the values X and Y inputted to the nuclear fuelmonitor control means 25. The fuel number processing means 44 stores therecognized characters of the nuclear fuel identification number and theX-Y ID coordinates of the positions K_(i) in an associated manner, anddisplays them on the display 46 and prints them out by the printer 47.Since the recognized characters of the nuclear fuel identificationnumber and the X-Y ID coordinates are associated, the nuclear fuelidentification number of the fuel assembly 66 loaded at the positionK_(i) of the fuel rack 65 in the fuel storage pool 63 can be readilydetermined.

In accordance with the nuclear fuel identification code reader of thepresent embodiment, the following advantages are offered.

Since the nuclear fuel identification number 74B marked by the lettersis recognized by the optical sensor and the nuclear fuel identificationcode monitor 28, the fuel assembly 66 in the fuel storage pool can beidentified in a short time. Even if it is difficult to recognize theletters of the nuclear fuel identification number 74B based on the videosignal from the optical sensor (due to the deposition of the clad to thehandle 72 of the fuel assembly 66 under consideration), it is possibleto readily recognize the letters of the nuclear fuel identificationnumber by the ultrasonic wave sensor and the nuclear fuel identificationmonitor 34. By the combined use of the detection of the primary nuclearfuel identification number by the optical sensor and the detection ofthe supplementary nuclear fuel identification number by the ultrasonicwave sensor, the nuclear fuel identification numbers marked on all fuelassemblies in the fuel storage pool 63 can be detected in a very shorttime with an accuracy of essentially 100% (99.99%). By preferentiallyusing the detection by the optical sensor to the fuel assembly 66 andsupplementarily using the detection by the ultrasonic wave sensor incase the letters of the nuclear fuel identification number 74B cannot berecognized based on the information derived from the optical sensor, theabove advantages, particularly the reduction of the detection time, areremarkable. In the present embodiment, for those of the fuel assemblies66 stored in the fuel storage pool 63 whose nuclear fuel identificationnumber 74B cannot be recognized by the optical sensor, the detection ofthe nuclear fuel identification number 74A by the ultrasonic wave sensoris effected. The automatic reading of the nuclear fuel identificationnumber may also be effected. In the present embodiment, since theultrasonic wave sensor detects the digitized recesses 75 formed on thetop 73 of the handle 72 of the fuel assembly 66, the processing time forrecognizing the letters can be significantly reduced compared to thatrequired in detecting the letters themselves by the ultrasonic sensor.In the present embodiment, the structure of the ultrasonic wave probescanner and the structure of the associated nuclear fuel identificationcode monitor (especially a processing program) can be simplifiedcompared to a case where the letters themselves are detected by theultrasonic wave sensor. The provision of the read reference recess 76 onthe top 73 of the handle 72 facilitates the recognition of the lettersof the nuclear fuel identification number 74A based on the reflectedultrasonic wave.

Since both the digitized (coded) nuclear fuel identification number 74Aand the nuclear fuel identification number 74B in letters are marked onthe top 73 of the handle of the fuel assembly 66, the detection by theoptical sensor and the detection by the ultrasonic wave sensor arefacilitated. The provision of the nuclear fuel identification number 74Balso permits visual recognition by a human.

Since the sensor handling unit 1 is provided in the nuclear fuelhandling unit 51, a portion of the nuclear fuel handling unit 51 can beutilized as the nuclear fuel identification code reader and the entireconstruction can be very compact. In other words, the fuel assembly maybe moved by the nuclear fuel identification code reader. In FIG. 1,separate movable truck and laterally movable truck such as grapple 54for handling the fuel may be provided, although the construction may becomplex. The nuclear fuel handling unit control means 24 may also beassembled in a separate computer.

The mounting of the ITV camera 5 and the ultrasonic wave probe scanner10 on one grapple 4 significantly contributes to the simplification ofthe structure. Since the drive mechanism (the drive motor 13 and therotary screw 14) for moving up and down the ultrasonic wave probe 9 isprovided separately from the grapple 4, the positioning of theultrasonic probe 9 above the fuel assembly is facilitated.

Since the nuclear fuel identification number 74A including the recesses65 is marked on the top 73 of the fuel assembly 66, the processing timerequired for the character recognition based on the reflected ultrasonicwave is essentially same as the processing time required for thecharacter recognition based on the detection of the nuclear fuelidentification number 74B by the ITV camera 5. However, the detection ofthe nuclear fuel identification number 74B by the ITV camera 5 can becontinuously effected while the movable truck 52 and the laterallymovable truck 53 are driven, but the detection of the nuclear fuelidentification number 74A by the ultrasonic sensor should repeat thestart and stop of the movement of the movable truck 52 and the laterallymovable truck 5 and the start and stop of the scan of the ultrasonicwave probe 9 for each fuel assembly 66. Accordingly, the time requiredto recognize the nuclear fuel identification numbers of all fuelassemblies is shorter when both the character recognition for the fuelidentification number 74B based on the video signal from the opticalsensor and the character recognition based on the reflected wave by theultrasonic wave sensor are used than when the characters of the nuclearfuel identification number 74A are recognized by the ultrasonic wavesensor.

Another embodiment of the nuclear fuel identification code reader of thepresent invention is explained with reference to FIGS. 16 and 17. Thelike elements to those shown in the embodiment of FIG. 1 are designatedby the like numeral. Most elements of the present embodiment areidentical to those of the embodiment of FIG. 1. In the presentembodiment, the nuclear fuel identification code processing unit 43 inthe embodiment of FIG. 1 is replaced by a nuclear fuel identificationcode compare unit 83. Configuration and operation of the nuclear fuelidentification code compare unit 83 are explained below. The nuclearfuel identification code compare unit 83 has a memory 45 and fuel numbercompare means 84. The fuel number compare means 84 receives the lettersof the nuclear fuel identification number recognized by the nuclear fuelidentification code monitor 28 or 34, and also receives an X-Y IDcoordinate of a position K_(i) based on the values X and Y inputted tothe nuclear fuel monitor control means 25 (step 85A). The memory 45stores the nuclear fuel identification number (in letters) of the fuelassemblies 66 at each position K_(i) of the fuel rack in the fuelstorage pool 63. Those are previously detected data. The memory 45 alsostores data representing the load status of the fuel assembly 66 fetchedfrom the memory 26 by the fuel number compare means 84. This dataindicates the presence or absence of the fuel assembly 66 at eachposition K_(i) of the fuel rack 65.

The fuel number compare means 84 compares the X-Y ID coordinate of theposition K_(i) inputted currently and the letters of the nuclear fuelidentification number for the position K_(i) with the corresponding pastdata read from the memory 45 (step 85B), and determines the matching(step 85C). The comparison result is stored in the memory 45, displayedon the display 46 and printed out by the printer 47. If the result inthe result in the step 85C is non-match, a buzzer is sound to alarm tothe operator.

In this manner, the present embodiment can attain the same advantages asthose of the embodiment of FIG. 1, and it is particularly effective inthe recognition of the fuel assembly 66 where the fuel assembly 66 is tobe stored in the fuel storage pool 6 for an extended period. By thecomparison of the letters of the current nuclear fuel identificationnumber and the past data previously detected, the storage of the fuelassembly 66 having the identical nuclear identification number in thefuel storage pool 63 can be readily checked.

Other embodiment of the nuclear fuel identification code reader of thepresent invention is explained below. As shown in FIG. 18, the presentembodiment uses a nuclear fuel identification code monitor 28A in placeof the nuclear fuel identification code monitor 28 of FIG. 1. Thenuclear fuel identification code monitor 28A comprises, in addition tothe elements of the nuclear fuel identification code monitor 28, ITVcamera control means 86 which receives a start of detection signal S₁from the nuclear fuel monitor control means 25. The ITV camera controlmeans 86 generates a start of image pickup trigger signal to the ITVcamera 5, a turn-on signal to the illumination unit 8, a start of inputsignal for the video signal to the video signal digitizer 29, and astart of image processing signal to the image processing means 31, inresponse to the input start of detection signal S₁. When the ITV camera5, the illumination unit 8, the image signal digitizer 29 and the imageprocessing means 31 receives those signals, they carry out the functionsassigned thereto as they do in the embodiment of FIG. 1. The presentembodiment also attains the same advantages as those of the embodimentof FIG. 1.

A software implemented embodiment of the image processing means 31 andthe fuel number identification/ discrimination means 32 of themicroprocessor 30 used in the nuclear fuel identification code monitor28 shown in FIG. 1 is explained with reference to FIG. 19. Amicroprocessor 30A which corresponds to the microprocessor 30 has inputmeans 87A, output means 87B, a CPU 87C, a RAM 87D and a ROM 87E. Theinput means 87A is connected to the video signal digitizer 29 and theinput output means 23B. The output means 87B is connected to theinput/output means 23B and the fuel number processing means 44. Aninternal bus 87F connects the input means 87A, the output means 87B, theCPU 87C, the RAM 87D and the ROM 87E in the microprocessor 30A. Thefunction of the memory 33 of the microprocessor 30 is effected by theRAM 87D. The output of the video signal digitizer 29 is stored in theRAM 87D. The ROM 87E stores the processing steps shown in FIGS. 9 and 10with the steps 78F and 79A being removed and the step 79B being executedafter the step 78E. In the present embodiment, the memory 33 of FIGS. 9and 10 is replaced by the RAM 87D. The CPU 87C recognizes the letters ofthe nuclear fuel identification number 74B based on the video signalfrom the ITV camera 5 in accordance with the process stored in the ROM87E.

A software implemented embodiment of the ultrasonic signal processingmeans 40 and the fuel number identification means 41 of themicroprocessor 39 used in the nuclear fuel identification code monitor34 of FIG. 1 is explained with reference to FIG. 20. A microprocessor39A corresponding to the microprocessor 39 has input means 89A, outputmeans 89B, a CPU 89C, a RAM 87D and a ROM 89E which are interconnectedthrough an internal bus 89F. The input means 89A is connected to theencoder 20 and the probe scanner control means 38. The output means 89Bis connected to the fuel number processing means 44. The function of thememory 42 of the microprocessor 39 is effected by the RAM 87D. Theprocessing steps shown in FIGS. 14 and 15 with the steps 81E and 82Abeing removed and the step 82B being executed after the step 81D arestored in ROM 87E. The CPU 87C recognizes the letters of the nuclearfuel identification number 74A based on the reflected ultrasonic wave inaccordance with the process stored in the ROM 89E.

In the embodiment of FIG. 1, the same advantages are attained when themicroprocessor 30 is replaced by the microprocessor 30A and themicroprocessor 39 is replaced by the microprocessor 39A.

The recesses 75 of the nuclear fuel identification number 74A marked onthe top 73 of the handle 72 of the fuel assembly 66 shown in FIG. 5 maybe of an upside-down conical shape at the bottom as shown in FIG. 21.Preferably, the bottom of the recess 75 does not have a flat area whichis parallel to the top 73. With such a shape, the scatter of theultrasonic wave radiated to the recess 75 is violent and the reflectedwave from the recess 75 back to the ultrasonic wave probe 9 is verylittle. As a result, the detection of the recess by the ultrasonic waveis facilitated.

The technical concept of the above embodiments may be utilized inrecognizing the nuclear fuel identification number marked on a fuelassembly of a pressured water type nuclear reactor.

Other embodiment of the nuclear fuel identification code reader of thepresent invention is explained with reference to FIG. 22. Unlike theabove embodiments, the nuclear fuel identification code reader of thepresent embodiment can be applied to a fuel assembly having no nuclearfuel identification code 74A marked on the top 73 of the handle 72. Itcan also recognize the nuclear fuel identification code 74B marked onthe top 73 of the handle 72 by any one of the output signals of theoptical sensor and the ultrasonic wave sensor.

The constructions of the nuclear fuel handling unit 51 and the sensorhandling unit 1 of the present embodiment are identical to those of theembodiment of FIG. 1. In the present embodiment, the nuclear fuelhandling control unit 22, the nuclear fuel identification code monitors28 and 34, and the nuclear fuel identification code processing unit 43in FIG. 1 are replaced by a nuclear fuel handling control unit 100,nuclear fuel identification code monitors 250 and 260 and a dataprocessing unit 240, respectively.

The nuclear fuel handling control unit 100 has input/output means 23Aand 23B, a nuclear fuel handling unit control means 24 and nuclear fueldetection unit control means 101. The input/output means 23A and 23Binput and output signals similar to those for the nuclear fuel handlingcontrol unit 22 between the nuclear fuel handling unit 51 and the sensorhandling unit 1. The nuclear fuel handling unit control means 24 and thenuclear fuel detection unit control means 101 are included in a computer48A.

The nuclear fuel identification code monitor 250 comprises imageprocessing means 140, a video signal digitizer 150, a video frame memory160, fuel number identification/discrimination means 170 andillumination control means 180. The functions of the image processingmeans 140, the image frame memory 160 and the fuel numberidentification/discrimination means 170 are effected by a microprocessor30A. The illumination control means 180 may also be constructed by themicroprocessor. The video signal digitizer 150 has the same function asthe video signal digitizer 29. The fuel numberidentification/discrimination means 170 is coupled to the input/outputmeans. The nuclear fuel identification code monitor 250 reads thenuclear fuel identification code by the video signal produced by the ITVcamera 5.

The nuclear fuel identification code monitor 260 comprises a signalprocessing microprocessor 39A, ultrasonic wave scanner control means 190and ultrasonic wave transmit/receive means 200. The microprocessor 39Ahas the functions of the ultrasonic wave signal processing means 210 andthe fuel number identification means 200A. The ultrasonic wave scannercontrol means 190 may also be constructed by the microprocessor. Theultrasonic wave transmit/receive means 200 comprises pulse generationmeans 35 and signal receive means 36. The pulse generation means 35 isconnected to the ultrasonic wave probe 9 and the ultrasonic wave scannercontrol means 190. The signal receive means 36 is connected to theultrasonic wave probe 9 and the ultrasonic wave signal processing means210. The ultrasonic wave signal processing means 210 is coupled to theencoder 20 and the fuel number identification means 200. The ultrasonicwave scanner control means 190 is connected to the drive motors 13 and17, the encoder 20 and the limit switch 37, and also to the input/outputmeans 23B and the fuel number identification means 200A. The fuel numberidentification means 200 is coupled to the input/ output means 23B andthe fuel number identification means 170. The nuclear fuelidentification code monitor 260 thus constructed recognizes the nuclearfuel identification code based on the reflected ultrasonic wave from theultrasonic wave probe 9.

The data processing unit 100 comprises fuel number processing means 44,a memory 45 and overall control means 241. The fuel number control means44 is connected to the display 46, the printer 47, the fuel numberidentification/discrimination means 170 and the fuel numberidentification means 200A. The overall control means 241 is connected tothe input/output means 23A and 23B, the fuel numberidentification/discrimination means 170 and the fuel numberidentification means 200. The memory 45 is connected to the fuel numberprocessing means 44 and the overall control means 241.

The console panel 270 is connected to the overall control means 241. Thedisplay 46 and the printer 47 may be arranged on the console panel 270.

The fuel assemblies 66A (BWR fuel assemblies) whose nuclear fuelidentification numbers are to be read by the present embodiment areloaded in the fuel rack 65. The fuel assembly 66A is of the samestructure as the fuel assembly 66. However, unlike the fuel assembly 60,the fuel assembly 66A has no nuclear fuel identification number 74Amarked on the top 73 of the handle 72. The recess 76 and engravednuclear fuel identification number 74B are marked on the top 73 of thefuel assembly 66A. The recess 76 has the same function as that in theembodiment of FIG. 1.

The operation of the nuclear fuel identification code reader of thepresent embodiment is now explained.

The operator designates the activation of one of the nuclear fuelhandling operation and the nuclear fuel identification code detectionunit through the console panel 270. The designated activation signal issupplied to the computer 48A. If the former activation signal isdesignated, the nuclear fuel handling unit control means 24 isactivated, and if the latter activation signal is designated, thenuclear fuel detection unit control means 101 is activated.

It is assumed that the designated operation is the nuclear fuel handlingoperation. The nuclear fuel handling activation signal designated by theoperator through the console panel 270 is supplied to the nuclear fuelhandling unit control means 24 through the overall control means 241 andthe input/output means 23A. Then, the nuclear fuel handling unit 51 iscontrolled by the nuclear fuel handling unit control means 24 as it isdone in the embodiment of FIG. 1. Like the memory 26, the memory 45stores the data relating to the load status of the fuel assembly 66A ateach position in the fuel rack 65. The data in the memory 45 is updatedwhen the load status of the fuel assembly 66A in the fuel rack 65 ischanged by the movement of the used fuel assembly 66A by the nuclearfuel handling unit 51. The data is updated by the overall control means241, which receives the related information from the nuclear fuelhandling unit control means 24.

When the activation of the detection unit is designated by the operatorthrough the console panel 270, the overall control means 241 producesthe detection unit activation signal. This signal is supplied to thenuclear fuel detection unit control means 101 through the input/outputmeans 23B. The overall control means 241 reads the positions of the fuelassemblies 66A (positions K_(i) on the chain line 49 starting at pointK₁) whose nuclear fuel identification numbers are to be detected, fromthe memory 45 and sequentially supplies them to the input/output means23B at a predetermined time interval. The nuclear fuel detection unitcontrol means 101 receives those signals and controls the movement ofthe sensor handling unit 1 in accordance with a process shown in FIG.24. The process shown in FIG. 24 is essentially identical to the processshown in FIG. 8. The process shown in FIG. 24 is different from theprocess shown in FIG. 8 in that a step 77N is executed after the step77F, and a step 77P is executed after the step 77J. The step 77N outputsthe position V_(i) of the ITV camera 5 determined based on the positionsignal representing the displacements X and Y measured by thesynchronous signal generators. The step 77P outputs a position W_(i) ofthe ultrasonic wave probe 9 determined based on the position signalrepresenting the measured displacements X and Y. The position signalW_(i) is produced when the fuel number identification means 170 producesa "1" output signal J (which is produced when all letters of the fuelidentification number 74B are not recognized). Signals representing thepositions V_(i) and W_(i) are produced by the input/output means 23B andsupplied to the fuel number identification means 170 and the fuel numberidentification means 200A. Like the nuclear fuel monitor control means25, the nuclear fuel detection unit control means 101 drives the ITVcamera 5 which is the optical sensor for the nuclear fuel identificationnumber onto the fuel assembly 66A under consideration, and drives theultrasonic wave probe 9 which is the ultrasonic wave sensor onto thefuel assembly 66A for the detection of the fuel identification number74B when it is difficult to recognize the fuel identification number 74Bdetected by the ITV camera 5.

Through the step 77F, the movable truck 52 and the laterally movabletruck 53 are driven and the ITV camera 5 is first moved toward theposition K₁. The fuel number identification means 170 receives thepositions V_(i) (X-Y ID coordinate) of the ITV camera 5 which aresupplied from time to time by the input/output means 23B through thestep 77M.

A portion of the process of the fuel numberidentification/discrimination means 170 is explained with reference toFIG. 27. The fuel number identification/discrimination means 170 inputs,in a step 79L, the predetermined position K_(i) (initially K₁) suppliedby the overall control means 241. In a step 79M, the position V_(i) isinputted. The position V_(i) is compared with the position K_(i) (step79N). If the decision in the step 79N is YES, it means that the ITVcamera 5 is on the fuel assembly 66A which is at the predeterminedposition K_(i). At this point, the fuel numberidentification/discrimination means 170 supplies the illumination unitturn-on signal to the illumination control means 180 although it is notshown in FIG. 27. The illumination control means 180 turns on theillumination unit 8 in response to this signal. The illumination unitturn-on signal is produced only when the initial position V₁ matches tothe initial predetermined position K₁. Then, the illumination unit 8 iskept turned on until the reading of the nuclear fuel identificationcodes for a predetermined number of fuel assemblies 66A is completed.The fuel number identification/discrimination means 170 produces a startof A/D conversion signal through the step 79P substantiallysimultaneously with the output of the illumination unit turn-on signal.The video signal digitizer 150 starts the A/D conversion of the videosignal for the top 73 of the handle 72 imaged by the ITV camera 5. Theimage signal converted to the digital signal by the video signaldigitizer 29 is supplied to the image frame memory 160 in 1/30 secondand stored in the image frame 160.

The image processing means 140 executes the process in accordance withthe steps shown in FIG. 25. The process shown in FIG. 25 includes steps78G-78I in addition to the steps shown in FIG. 9. After the steps78A-78C, the step 78D is carried out. In the step 78D, one of intensitylevels 0-255 is assigned to each of a number of pixels corresponding toone character (MXN pixels) in accordance with an image signal level ofthe corresponding portion. The rank 0 is darkest and the rank 255 isbrightest. In the step 78G, a frequency distribution of the rank (FIG.26) is determined in accordance with the intensity rank of each pixel.The frequency distribution is a distribution of number of pixels havingthe same intensity rank. A difference between a minimum frequencydistribution and a maximum frequency distribution is compared with apredetermined value (step 78H). If the difference is not greater thanthe predetermined value, it means that the status in the binarization isnot good, and a change of intensity signal is produced (step 78I). Theillumination control means 180 receives the change of intensity signalto increase the intensity of the illumination unit 8. The time requiredfor processing the above can be reduced to approximately 0.1 second byusing a high speed illumination method such as a stroboscopeillumination. After the intensity has been changed, the nuclear fuelidentification number 74B is picked up by the ITV camera 5. If thedecision in the step 78H is YES, the image signal is binarized in thestep 78E to prepare the character pattern of the character. Thebinarization of the image signal is effected by selecting "1" for thesignal which is larger than a predetermined reference between theminimum intensity rank and the maximum intensity rank of FIG. 26, andselecting "0" for the signal which is smaller than the predeterminedreference. Then, the step 78F is carried out.

After the step 78F, the fuel number identification/discrimination means170 sequentially carries out the steps 79A-79K shown in FIG. 10 as shownin FIG. 27. If the decision in the step 79F is NO, a "1" output signal Jis produced in the step 79K as it is in the previous embodiment. The "1"output signal J means that the discrimination of the nuclear fuelidentification number 74B by the ITV camera 5 is impossible due to thedeposition of the soft clad. The "1" output signal J is also a signal torequest redetection of the nuclear fuel identification number 74B by theultrasonic wave probe 9.

When the fuel number identification/discrimination means 170 producesthe "1" output signal J, the nuclear fuel detection unit control means101 carries out the step 77J. The fuel number identification means 200of the nuclear fuel identification code monitor 260 carries out thesteps 76L-79P shown in FIG. 27. The predetermined position K_(i) isinputted (step 79L). Then, the position W_(i) of the ultrasonic waveprobe 9 which varies from time to time and is produced by the nuclearfuel detection unit control means 101 in the step 77N is inputted. Ifthe position W_(i) matches to the predetermined position K_(i), thestart of detection signal S₂ is produced.

The ultrasonic wave scan unit control means 190 carries out the steps80B-80G shown in FIG. 12 when it receives the start of detection signalS₂. The ultrasonic wave probe scan unit 10 is controlled by the signalwhich is derived through the steps 80B, 80C and 80E-80G.

The signal receive means 36 receives the reflected wave signal detectedby the ultrasonic wave probe 9. The reflected wave is supplied to theultrasonic wave signal processing means 210. The ultrasonic wave signalprocessing means 210 carries out the process shown in FIG. 28. In a step81A, the reflected ultrasonic wave signal and the position signal of theultrasonic wave probe 9 detected by the encoder 20 are inputted. Thebinarization of the reflected wave signal in a step 81F is effectedbased on a time difference between the reflected wave signals of thefocused ultrasonic wave beam radiated from the ultrasonic wave probe 9.The focused ultrasonic wave beam from the ultrasonic wave probe 9 isradiated normally to the top 73 of the handle 72 and the bottom 91 ofthe nuclear fuel identification number 74B (FIG. 29). The time at whichthe reflected wave signal for the top 73 is represented by t₁ (FIG.30A), and the time at which the reflected wave signal for the bottom 91is received is represented by t₂ (FIG. 30B). A time to represent thetime at which the focused ultrasonic wave beam is radiated. A time t_(s)(=(t₂ -t₁)/2) is set as a threshold level. If the reflected ultrasonicwave signal is detected at a time t where t_(s) >t, "0" is assigned tothe position of the ultrasonic wave probe 9 at which the signal isdetected. If the reflected ultrasonic wave signal is detected at a timet where t_(s) ≦t, "1" is assigned to the position of the ultrasonic waveprobe 9 at which the signal is detected. In this manner the reflectedwave signal is binarized. In the present embodiment, the method 2) isused as it is in the previous embodiment. In the present embodiment,three or more ultrasonic wave probes 9 are arranged in parallel. In astep 81G, character patterns of the characters of the nuclear fuelidentification number 74B are prepared in accordance with the positionsignal of the ultrasonic wave probe 9 and the binary signal produced inthe step 81F. The prepared character patterns are supplied to the fuelnumber identification means 200 (step 81H). The fuel numberidentification means 200 carries out the steps shown in FIG. 31 whichare essentially same as the steps shown in FIG. 10. If the decision inthe step 79F is NO, the process is terminated.

The fuel number processing means 44 stores the characters of the nuclearfuel identification code 74B identified by the nuclear fuelidentification monitor 250 or 260 and the corresponding X-Y IDcoordinates of the positions K_(i) in the memory 45. It also displaysthem on the display 46 and prints them out by the printer 47 as may berequired.

The present embodiment also attains the same advantages as those of theembodiment of FIG. 1. However, since the nuclear fuel identificationnumber 74B is detected by the ultrasonic wave probe 9 in the presentembodiment, a longer recognition time is required than a case where thenuclear fuel identification number 74A is detected.

Other embodiment of the nuclear fuel identification code reader of thepresent invention is explained with reference to FIGS. 32 and 33. In thepresent embodiment, a Chelencoff light camera 93 and a nuclear fuelmonitor 280 are added to the embodiment shown in FIG. 22. The Chelencofflight camera 93 is mounted on the mount table 6 (FIG. 2) of the sensorhandling unit 1. The nuclear fuel monitor 280 has a video signaldigitizer 110 and a signal processing microprocessor 94 as shown in FIG.33. The microprocessor 94 has an image frame memory 120, nuclear fueldata processing means 130 and image processing means 140A. The videosignal digitizer 110 is coupled to the Chelencoff light camera 93. Thenuclear fuel data processing means 130 is coupled to the input/outputmeans 23B, the fuel number processing means and the overall controlmeans 241.

The present embodiment has means for determining if the used fuelassembly 66A stored in the fuel storage pool 63 is a real fuel assemblywhich contains the nuclear fuel. This means comprises the Chelencofflight camera 93 and the nuclear fuel monitor 280. The Chelencoff lightcamera 93 detects only a light in an ultraviolet range (Chelencofflight) emitted in water by a gamma ray emitted from a nuclear fissionseed, amplifies it by a photo-multiplier and directs the amplifiedelectrons to a phosphor plane to visualize them. The image picked up bythe Chelencoff light camera 93 has a high intensity at an areacorresponding to the water region surrounded by the fuel rods whichcontain the nuclear fuel.

The nuclear fuel detection unit control means 101A of the nuclear fuelhandling control unit 100 controls the movement of the sensor handlingunit 1 in accordance with a process shown in FIG. 34. In the processshown in FIG. 34, steps 77Q and 77R are added between the steps 77N and77H of the process shown in FIG. 24. After the movement of the ITVcamera 5 in the step 77F, the Chelencoff light camera 93 is moved to theposition K_(i) in the step 77Q. The position U_(i) of the Chelencofflight camera 93 thus changes from time to time, and the position U_(i)is outputted (step 77R).

The position U_(i) outputted by the input/output means 23B is suppliedto the nuclear fuel data processing means 130. The nuclear fuel dataprocessing means 130 carries out the steps 79L-79P shown in FIG. 27 andsupplies the start of A/D conversion signal to the video signaldigitizer 110. The video signal digitizer 110 starts the A/D conversionof the video signal supplied from the Chelencoff light camera 93, inresponse to the start signal. The video signal converted to the digitalsignal is stored in the image frame memory 120 as the image signal.

The image picked up by the Chelencoff light camera 93 does not alwayshave a high S/N ratio. When it is to be determined whether the nuclearfuel is contained in the fuel assembly 66A, no special image processingis required for the video signal picked up by the Chelencoff lightcamera 93. However, in order to determine whether the nuclear fuel iscontained or not in the fuel assembly to prepare a Chelencoff lightpattern, the following processing is required. This image processing isdone by the image processing means 140A. FIG. 35 shows the imageprocessing means. An image signal is supplied from the image framememory 120 (step 78A). A plurality of frame images taken time-seriallyare combined for each pixel (step 78G). A noise component of the imagesignal is reduced by the combination and the S/N ratio of the imagesignal is enhanced. The image signal produced in the step 78G isvignetted (step 78H). Through this step, an RF noise component iseliminated from the image signal. The image signal having the RF noisecomponent eliminated is binarized with a proper binarization level (step78I). The binary data is supplied to the nuclear fuel data processingmeans 130. The Chelencoff light pattern is created based on the binarydata (step 79Q). FIG. 37 shows the Chelencoff light pattern created inthe step 78J. In FIG. 37, numeral 70A denotes a fuel rod and numeral 72Adenote a handle. The fuel rods which contain the nuclear fuel aredistinguished from other elements such as water rods which do notcontain the nuclear fuel, and they are patterned. Based on theChelencoff light pattern thus created, whether the fuel assembly 66Aunder consideration is the true fuel assembly which contains the nuclearfuel or not is determined (step 79R). The decision and the Chelencofflight pattern are supplied to the fuel number processing means (step79S).

The fuel number processing means 44 carries out the same steps as thoseof the fuel number processing means 44 of the embodiment shown in FIG.22, as well as the following steps. If the decision in the step 79R is"true fuel assembly", a reference Chelencoff light pattern correspondingto the nuclear fuel identification number 74B recognized by the nuclearfuel identification code monitor 260 or 280, and the Chelencoff lightpattern created in the step 79Q are compared. Through the comparison, itis determined whether the recognized nuclear fuel identification number74B is correct or not. The result of this determination and the decisionin the step 79R are displayed on the display 46.

The present embodiment can attain the same advantages as those of theembodiment of FIG. 22. In the present embodiment, it is determinedwhether the fuel assembly 66A whose nuclear fuel identification number74B is to be detected is true fuel assembly which contains the nuclearfuel or not. In the present embodiment, the correctness of the nuclearfuel identification number 74B recognized based on the Chelencoff lightpattern can be checked and the accuracy of recognition of the nuclearfuel identification number is improved.

In the embodiment shown in FIG. 32, since the Chelencoff light camera 93is driven directly above the handle 72 of the fuel assembly 66A underconsideration, the image of the handle 72 is patterned as shown in FIG.37. As a result, the pattern of the fuel rods located directly below thehandle 72 is not created. This problem may be solved by inclining theChelencoff light camera 93 around the handle 72 by an angle θ on eachside and picking up the top of the fuel assembly 66A from two directionsG₁ and G₂, as shown in FIG. 38. The Chelencoff light camera 93 may berotated in a direction 95 by a motor (not shown) mounted on the mounttable 6. The video signals picked up by the Chelencoff light camera 93from the directions G₁ and G₂ are supplied to the nuclear fuel monitor280. Those video signals are converted to digital signals by the videosignal digitizer 110 and they are stored in the image frame memory 120.The image processing means 140A processes those image signals for thedirections G₁ and G₂ to produce binary data. In a step 79Q of thenuclear fuel data processing means 130, the Chelencoff light patternscreated based on the video signals picked up from the directions G₁ andG₂ are combined to create a new Chelencoff light pattern (FIG. 39A). TheChelencoff light pattern created based on the data of the direction G₁is shown in FIG. 39B, and the Chelencoff light pattern created based onthe data of the direction G₂ is shown in FIG. 39C. The Chelencoff lightpattern of FIG. 39A is created by image combination of a triangularpattern at right bottom of FIG. 39B and a triangular pattern at left topof FIG. 39C. In the Chelencoff light pattern of FIG. 39A, the handleshown in FIG. 39B and 39C (in broken lines) disappears. Accordingly, theChelencoff light pattern located directly below the handle is created.

The above embodiments are designed to read the nuclear fuelidentification number marked on the BWR fuel assembly 66. The PWR fuelassembly 66B has the nuclear fuel identification number marked on theside of the top tie plate. A structure of an optical sensor which canread the nuclear fuel identification numbers marked on both types offuel assemblies is shown in FIGS. 40A and 40B. FIG. 40A shows a readstatus for nuclear fuel identification number 74B marked on the fuelassembly 66. FIG. 40B shows a read status for the fuel assembly 66B.When this optical sensor is applied to the fuel assembly 66, areflection mirror 96 supported by the ITV camera 5 is placed in parallelto the axis of the ITV camera 5. When it is applied to the fuel assembly66B, the frame 7 and the illumination unit 8 are removed and areflection mirror tube 97 is mounted on the mount table 6 instead, asshown in FIG. 40B. The reflection mirror tube 97 has a pair ofreflection mirrors 99 at the top and the bottom thereof, and has anillumination unit 98 mounted at the lower end. The reflection mirror 96is rotated to be obliquely to the axis of the ITV camera 5. The lowerend of the reflection mirror tube 97 is inserted between the stored fuelassemblies 66B. The image of the nuclear fuel identification number 74Bmarked on the side at the upper end of the fuel assembly 66B is directedto the ITV camera 5 through the pair of reflection mirrors 99 and thereflection mirror 96.

The optical sensor shown in FIGS. 40A and 40B is applicable to thenuclear fuel identification code readers of the above embodiments.

What is claimed is:
 1. A fuel assembly comprising:an upper tie platehaving a first nuclear fuel identification code and a second nuclearfuel identification code of a different expression from that of thefirst nuclear fuel identification code, marked adjacently to each other;a lower tie plate; and a plurality of fuel rods having opposite endsthereof held by said upper tie plate and said lower tie plate.
 2. A fuelassembly according to claim 1 wherein said upper tie plate includes ahandle having the first nuclear fuel identification code expressed bycharacters and the second nuclear fuel identification code of thecorresponding content expressed by a plurality of separate recessesformed in adjacent to the first nuclear fuel identification code.
 3. Afuel assembly according to claim 2 wherein said handle has an additionalrecess formed on the top thereof, said additional recess having adifferent width than the width of the recesses constituting the secondnuclear fuel identification code and, serving as a read reference forthe second nuclear fuel identification code.